Skip to main content
SpringerLink
Log in

Prospects for the development of a direct-flow vessel reactor with superheated steam

  • Published:
Atomic Energy Aims and scope

Abstract

A system of new technical solutions, which will make it possible to develop a reactor system using a coolant with supercritical parameters and efficiency 44%, solving the main problems of the nonuniformity of coolant heating in the core, is examined. This sytem contains a core based on fuel micropellets, a multistep fuel assembly with transverse coolant flow, coolant mixing after each step, and continual reloading of fuel micropellets into each fuel assembly.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Log in via an institution

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Institutional subscriptions

Similar content being viewed by others

References

  1. P. L. Kirillov, “Supercritical parameters: a future for reactors with water coolant and nuclear power plants,” At. Tekh. Rubezh., No. 6, 3–8 (2001).

  2. A Technology Road Map for Generation IV Nuclear Energy Systems, issued by the US DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum, December 2002.

  3. Y. Oka and K. Koshizuka, “Supercritical-pressure, light-water-cooled reactors for improving economy, safety, plutonium utilization, and environment,” Progress in Nucl. Energy, 39, 431–438 (1995).

    Article  Google Scholar 

  4. Y. Oka and K. Katoaka, “Conceptual design of fast breeder reactor cooled by supercritical steam,” Ann. Nucl. Energy, 19(4), 243–247 (2001).

    Article  Google Scholar 

  5. History of Atomic Energy in USSR and Russia, IzdAt, Moscow (2003), No. 3.

  6. History of Atomic Energy in USSR and Russia, IzdAt, Moscow (2003), No. 2.

  7. V. A. Grigor’ev and V. M. Zorin (eds.), Handbook of Thermal and Nuclear Power Plants, Énergoatomizdat, Moscow (1982), pp. 326–328.

    Google Scholar 

  8. F. Ya. Ovchinnikov, V. A. Voznesenskii, and V. V. Semenov, Operating Regimes of VVÉR Reactors, Énergoatomizdat, Moscow (1992).

    Google Scholar 

  9. A. Ya. Kramerov and Ya. V. Shevelev, Engineering Calculations of Nuclear Reactors, Atomizdat, Moscow (1964).

    Google Scholar 

  10. A. I. Klemin, Engineering Probabilistic Calculations in Designing Nuclear Reactors, Atomizdat, Moscow (1973).

    Google Scholar 

  11. N. N. Ponomarev-Steppnoi, G. A. Filippov, E. I. Grishanin, et al., “Prospects for using fuel micropellets in VVÉR reactors,” At. Énerg., 86, No. 6, 443–449 (1999).

    Google Scholar 

  12. Hydraulic Calculation of Boiler Units. Normative Method, Énergiya, Moscow (1978).

Download references

Author information

Authors and Affiliations

  1. All-Russia Research Institute of Automatic Machines, Russia

    G. A. Filippov, E. I. Grishanin, L. N. Fal’kovskii & B. I. Fonarev

  2. Russian Science Center Kurchatov Institute, Russia

    P. N. Alekseev, N. E. Kukharkin, P. A. Fomichenko, V. F. Tsibul’skii & A. V. Chibinyaev

Authors
  1. G. A. Filippov
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. E. I. Grishanin
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. L. N. Fal’kovskii
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. B. I. Fonarev
    View author publications

    You can also search for this author in PubMed Google Scholar

  5. P. N. Alekseev
    View author publications

    You can also search for this author in PubMed Google Scholar

  6. N. E. Kukharkin
    View author publications

    You can also search for this author in PubMed Google Scholar

  7. P. A. Fomichenko
    View author publications

    You can also search for this author in PubMed Google Scholar

  8. V. F. Tsibul’skii
    View author publications

    You can also search for this author in PubMed Google Scholar

  9. A. V. Chibinyaev
    View author publications

    You can also search for this author in PubMed Google Scholar

Additional information

__________

Translated from Atomnaya Énergiya, Vol. 100, No. 3, pp. 197–204, March, 2006.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Filippov, G.A., Grishanin, E.I., Fal’kovskii, L.N. et al. Prospects for the development of a direct-flow vessel reactor with superheated steam. At Energy 100, 192–198 (2006). https://doi.org/10.1007/s10512-006-0072-x

Download citation

  • Received:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-006-0072-x

Keywords

Search

Navigation